05000271/LER-1993-004

LER 93-004-01:on 930225,discovered That Surveillance for Jet Pumps Not Performed During Single Loop Operations Due to Inadequate Plant Procedures.Procedures OP-4110 & OP-2428 revised.W/930819 Ltr

ML20056E419
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	08/19/1993
From:	Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-93-069, BVY-93-69, LER-93-004, LER-93-4, NUDOCS 9308240014
Download: ML20056E419 (4)

LER-2093-004,

Event date:
Report date:
2712093004R00 - NRC Website

text

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't VERMONT YANKEE NUCLEAR-POWER CORPORATION l

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\ ;,' -} Vernon Vermont 05354-0157  !

(602) 257-7711 i

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l U.S. Nuclear Regulatory Commission' i Document Control Desk )

Washington, D.C. 20555

REFERENCES:

Operating License DPR-28 ,

4 Docket No. 50-271 Reportable Occurrence No. LER 93-004, Supplement 1 l BVY 93-069, VYNPC Letter to NRC Dated July 2, 1993

Dear Sirs:

I As defined by 10 CFR 50.73, we are reporting the attached Reportable Occurrence as LER 93-004, Supplement 1. This supplement is submitted to provide  :

an update on our root cause assessment and planned course of action. l I

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very truly yours, j

, VERMONT YANKEE NUCLEAR POWER CORPORATION l MT . e r- ,

Robert Wanczyk ,

Plant Manager j t

cc: Regional Administrator USNRC Region I i 475 Allendale Road King of Prussia, PA 19406 l 0

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/ l) 9308240014 930819 j- L PDR ADOCK 05000271  ;

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'WRC Fore 366 U.S. C]UCLEQR REGULATORY COMMISSION APPR0trED OMS No. 3150-0104 (6-89)* EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTI M TE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY COMMIS$10N, WASHINGTON DC 20555, AND TO THE PAPERbORK REDUCTION PROJECT (3160 0104), OFFICE OF MANAGEMCNT AND BUDGET, WASHINGTON, DC 20603. ,

FACILITY KAME (1) DOCKET No. (2) PAGE (3)

VERMONT YAhKEE NUCLEAR POWER STATION Ol5l0l0l0l2l7l1 0 1 0F 0 3 TITLE (4) Jet Pmp Operability Surveillance not Performed during Single loop Operations as Required by Technical Specifications Due to inadequate plant procedures.

f EVENT LATE (5) LER NUMEER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (B) )

MONTH DAY YEAR YEAR SEQ # REV # MONTH DAY YEAR FACILITY NAMES DOCKET NO. (S) 0 5 0 0 0 0 2 2 5 9 3 9 3 -

0 0 4 -

0 1 0 8 1 9 9 3 0 5 0 0 0 OPERATING THIS REPORT IS SUEMITTED PURSUANT TO REC'MTS OF 10 CFR 1: CHECK ONE OR MORE (11) i MT>E (9) W 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) ,

POWER 20.405(s)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) '

LEVEL (10) 0l9l9 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER:

.. ... ......... 20.405(a)(1)(iii) x 50.73(a)(2)(1) 50.73(a)(2)(viii)(A)

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........ . .. . .. 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B)

..... . . .... 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICEhSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NO.

AREA CODE ROBERT J. WANCZYK, PLANT MAkAGER Bl0l2 2l5l7l-l7l7l1l1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIEED IN THIS REPORT (13)

CAUSE SYST COMP 0hEhi MFR REPORTABLE CAUSE SYST COMPOWENT MFR REPORTABLE To hPRDS .... TO WPRDS ....

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SUPPLEMENTAL REPORT EXFtCTED (14) EXPECTED MO DAY YR SURMIS$10N DATE (15)

YES (if yes, conplete EXPECTED SUBMISSION DATE) X NO l l l ABSTRACT (Limit to 1400 spaces, i.e., approx. fif teen single-space typewntten lines) (16)

On 11/9/92 at 1429 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.437345e-4 months <br />, with the reactor at approxirnately 99% power, the "A* Recirculation Pump Motor Generator (EltS = AD MG) Set tripped due to electrical proolems. From 11/9/92 at 1429 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.437345e-4 months <br /> until 11/13/92 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> the plant was in single loop operation. On 2/25/93, during a review of the surveillance, it was discovered that the required surveillance for the Jet Pumps (Ells = AC P) in the idle loop, during single loop operation was not performed in accordance with Technical Specification 4.6.F.2 The root cause of this event was our failure to ensure that Technical Secifications requirements were appropriately incorporated into the plant procedures.

The plant had returned to two loop operation prior to the time of discovery of the event. The immediate corrective action was to revise OP-4110, " Reactor Recirc Surveillance" and OP-2428,

• Single Loop Operations *, to provide specific instructions to correct this problem. Additionalty, Procedure OP-4110 has been revised to include OP-2428 as a reference.

No similar events have been reported to the Commission in the last five years.

CIRC Form 366 (6 89)

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, ERC Form 366A U.S. NUCLEAR DEGULATORY COMMISSION APPROVED OMS NO. 3150-0104 (6-BP) EXPIRES 4/30/92 i EST!nATED BURDEN PER RESPONSE TO COMPLY WITH THIS f INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD }

LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE 10 THE RECORDS AND TEXT CONTINUATION REPORTS MANAGEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND j BUDGET, WASHINGTON, DC 20603. ,

FACILITY NAME (1) DOCKET NO (2) LER WUMBER (6) PAGE (3)

TEAR SEQ # REV #

9 3 4 0 0 0 0l2 0F 0l3 VERMONT YANKEE NUCLEAR POWER CORPORATION 0l5l0l0j0l2l7l1 1 TEXT (if more space is required, use additional NRC Form 366A) (17)

DESCRIPTION On 11/9/92 at 1429 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.437345e-4 months <br />, with the reactor at approximately 99% power, the *A* Recirculation Pump Motor i Generator (Ells = AD MG) tripped due to electrical problems. On 2/26/93, it was discovered that the required surveillance for '

the Jet Pumps (Ells = AC P) in the idle loop during single loop operation was not performed in accordance with Technical Specification 4.6.F.2. From 11/9/92 at 1429 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.437345e-4 months <br /> until 11/13/92 at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> the plant was in single loop operation to  !

facilitate repair of the MG set. During this period the data for jet pump surveillance was acquired on a daily basis, as required I by procedure, and operability was determined to be satisf actory for the active loop, however, although data was also taken for ]

the idle loop, no specific evaluation was made concerning the jet pumps in the idle loop. On 11/13/92, the *A* Recirc Pump ]

MG Set was returned to service and jet pump operability was determined to be satisf actory for both recirculation loops.  !

CAUSE OF EVENT The root cause of this event was a f ailure to ensure that Technical Secifications requirements were appropriately incorporated into the t 'nt procedures.

ANALYSIS OF EVENT Prior to the trip and following restart of the *A* Recirc MG Set, iet pump operability surveillance was completed on a daily basis for both recirc loops. The data taken was within the Technical Specification limits which proved the operability and integrity of the jet pumps in both loops. During the period of single loop operation, data was taken and operability and integrity was confirmed for the active loop in accordance with Technical Specification 4.6 F.1. Following start-up of the "A" Recirc MG Set, Jet pump operability surveillance was completed for both loops and operability and integrity was again confirmed . During single loop operations, there was flow indication in each of the idle loop jet pumps. This is a further indication of operability.

j GE SIL No. 517, issued on July 26,1990, specifically addresses single loop operation and jet pump integnty. It states that "dunng single loop operation, the inactive loop jet pumps are not operating and the stress applied to the jet pump beam, that holds the removable portion of the iet pump in place, is much less than it is when the pumps are operating. Consequently, if the jet pump is intact before entering single loop operation, it is not likely to degrade during single loop operation and surveiitance of the inactive loop jet pumps is not necessary*

Based on the above, there was no threat to the health and safety of the public due to this event.

1 CORRECTIVE ACTIONS

immediate Corrective Actionj There was no immediate corrective actions required as the date of discovery occurred af ter the plant returned to two loop operation.

Subsecuent Corrective Actions OP 4110, " Reactor Recirc Surveillance" and OP-2428, ' Single Loop Operations", have been revised to provide specific

instructions to correct this problem. Additionally, Procedure OP-4110 has been revised to include OP-2428 as a reference. l z

Lono Term Corrective Actions A review of procedures that implement Technical Specification surveillance requirements will be performed to ensure that Technical Specification requirements are being met. This review will address such items as the intent of the Technical Specifications survei!!ance requirements, assumptions, trending, administrative limits, and the clarity of procedure insrtuctions.

hRC Form 366 (6-89)

i h2C Form 366A U.S. 05UCLEAR REGULATORY COMMIS$10N APPROVED OMS NO. 3150-0104

-(6.89) EXPlaES 4/30/92 l ESTIMATED BURDEN PER DESPONSE TO COMPLY WITH THIS i i

INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ES11 MATE TO THE RECORDS AND

• LICEk%EE EVENT REPORT (LER) ,

TEXT CONTINUATION REPORTS MANAGEMENT BRANCH (P-350), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON DC 20555, AND TO THE PAPERWORK .

REDUCTION FROJECT (3160-01D4), OFFICE OF MANAGEMENT AND  !

BUDGET, WASHINGTON, DC 20603.

FACILITY hAME (1) DOCKET NO (2) LER WUMBER (6) PAGE (3)

YEAR SEQ # REV #

VERMONT YANKEE NJCLEAR POWER CORPORATION 0l5l0l0l0l2l7l1 9 3 -

0 0 4 -

0 1 0l3 CF 0l3 TEXT fit more space is required, use additional NRC Form 366A) (17)

Lona Term Corrective Actions (CONT.)

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Based on the information from GE SIL No. 517, Vermont Yankee will request a revision to the Technical Specifications l l to delete the requirements of Section 4.6.F.2. This is expected to be submitted by November 1993.

ADDITIONAL INFORMATION There have been no similar events at Vermont Yankee reported to the Commission in the past five years. '{

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CIRC Form 366A (6-89) ,

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